2009 FNCA Workshop on Research Reactor Utilization consisted of 2 workshops on sub-projects, namely Research Reactor Technology (RRT) and Neutron Activation Analysis (NAA). The activities of both 2 projects are supposed to be performed for 3 years including this second year.

FNCA workshop on RRT project

The objective of the RRT project, "Safety Analyses of RIA (Reactivity Initiated Accident) and LOFA (Loss of Flow Accident) for Research Reactors", is to improve and equalize the level of safety analysis techniques among participating countries to assure the safe and stable operation of research reactors for the promotion of effective utilization.
Each country has reported thermal-hydraulics calculation results of domestic reactors by using the COOLOD-N2. It was reported that the results agreed well with their own code results or experimental data.
Another common code EUREKA2/RR that was Nuclear & thermal-hydraulic coupling code for transient change, was attempted to be commoditized among the participants through some demonstrations and also execution of the sample problem with it. All participants agreed to carry out the reactivity-initiated accidents and loss of flow accidents of their domestic reactors with EUREKA2/RR. The results will be reported at the next FNCA workshop.
Information and experience on thermal hydraulic analyses were well exchanged among participants. Especially, the academic lecture by Prof. K. Mishima was useful and has given a wide and deep view for thermo-hydraulics of research reactors to participants.
He stressed the execution of the safety analyses without sufficient and comprehensive understanding on the analysis codes could induce variability in individual calculation values. That is so-called "User effects".
Design of Advanced Irradiation Capsules was proposed for theme of the next RRT-project, tentatively.

Neutron Activation Analysis is an elements analysis method by measuring the radioactivity and energy of activated elements in the sample irradiated by neutron beam. This method has an excellent beauty that is able to analyze all elements in the sample at once without any destruction. The project is performing the activities for the promotion of utilization on 3 themes that may be expected to make great socio-economic contribution. In the workshop, participants discussed about the current status of NAA utilization using the research reactor, progress of NAA domestic activities, future plan and so on.

A suggestion was made that a high-quality brochure could be produced by the FNCA to promote the applications and benefits of NAA in the field of geoscience.

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A proposal was received to undertake a laboratory inter-comparison of three different types of sediment materials. In this research, the common and unknown geochemical samples that Japan provides are analyzed by participating laboratories using NAA or related techniques. The result of the analysis is supposed to be compared to each other. It is expected that a journal paper would be written on this work. and the beauty of NAA analysis could be propagated in the world for better utilization of NAA.

Monitoring of food contaminants

Participating countries :

China, Indonesia, Korea, Malaysia, Thailand, Vietnam

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The elemental concentration level of the rice samples which had been selected as a common target material was discussed. Arsenic concentration in the rice samples was estimated to be less than the permissible (regulation) limit of each country.

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Tea was chosen as a common target sample for the next year's FNCA workshop, since it is so popular to the participating countries and expected to contain higher elemental contents than other plant samples.

Monitoring of environmental contamination

Participating countries :

Bangladesh, Indonesia, Japan, Malaysia, The Philippines, Vietnam

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Core sampling method was agreed to detect the past environment as well as surface sampling for monitoring spatial changes of contaminants.

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Hopefully, (210)Pb method can be a common protocol to know the sedimentation rate among FNCA countries.

Open symposium

Following FNCA Open symposium was held at Hachinohe Institute of Technology on September 10. About one hundred participants attended the event.

Theme :

"Nuclear human resource development for the future and Expectation of the role in Aomori region"

Opening Remarks

Mr. Keiichi Hakozaki,

Deputy Director-General, Research and Development Bureau, Ministry of Education, Culture, Sports, Science and Technology (MEXT)

Mr. Ikuo SASAKI,

Director General, Energy Policy Bureau, Aomori Prefectural Government

Dr. Eng. Masami Shoya,

President, Hachinohe Institute of Technology

Lecture

1.

Education and Research activities on Energy and Environment including Nuclear power in the Hachinohe region

"Education and research activities in "Hachinohe Institute of Technology" and Approach and Action for the regional issue"

"Nuclear human resource development for the future and Expectation to the role in
Aomori region"

Moderator :

Dr. Sueo Machi

Panelists :

Prof. Keizo Ishii,

Professor, Tohoku University Graduate School of Engineering Department of Quantum Science and Energy Engineering

Dr. Eng. Katsunori Abe,

Professor, Head of Research Institute for Interdisciplinary Science, Hachinohe Institute of Technology

Dr. Kiyonobu YAMASHITA

Prof. Mitsuru Ebihara

Above panelists presented positive comments or ambitions about the role of Aomori region from a global viewpoint for nuclear human resource development there.

Technical Visit

Participants of FNCA workshop moved to Rokkasho-mura on September 11 and visited following sites;
- Institute for Environmental Sciences
- Aomori Research and Development Center, Japan Atomic Energy Agency
- Japan Nuclear Fuel Ltd.

2009 FNCA Workshop on Research Reactor Utilization was held at the city of Hachinohe, Aomori prefecture, Japan. This event consisted of 2 workshops on sub-projects, namely Research Reactor Technology (RRT) and Neutron Activation Analysis (NAA). The activities of both 2 projects are supposed to be performed for 3 years including this second year.

Opening Session < RRT and NAA joint event >

Mr. Takashi Tadokoro, the representative of MEXT Japan, gave the opening remarks emphasizing the significance of FNCA activities. Regarding NAA activities, he stressed the importance to clarify the advantage of NAA and to make linkage with end-users. Similarly regarding RRT, he desired the practice in the workshop would advance safer and more stable operation of research reactor in the member countries.

Dr. Sueo Machi, FNCA Coordinator of Japan, reported FNCA activities in 2008 and 2009 focusing on major achievements of projects. He also reported conclusion and recommendation of the Ministerial Meeting in 2008 and 10th Coordinator Meeting in 2009. Review policy and plan by FNCA coordinators at 11th Coordinator Meeting were informed. Project leaders of RRU were requested to report the results of the workshop to coordinators.

The objective of RRT is to improve and equalize the level of safety analysis techniques among participating countries to assure the safe and stable operation of research reactors for the promotion of effective utilization.

Dr. Yamashita emphasized the utilization of research reactor was based on safe and stable operation, and human resource development was essential for it.

The objective of NAA is to exchange the up-to-date information on NAA and NAA-related matter of each participating country among FNCA countries and promote the use of NAA to end-users. As the workshop at Hachinohe is being held at the turning point of the three-years term, Prof. Ebihara requested all participating members to present the progress of NAA project for the first half of the term and to confirm goals of three subprojects (geochemical mapping and mineral exploration, monitoring of food contaminants and monitoring of pollutants in marine sediments) for full period.

After self-introduction, all participants were separated into either group of RRT or NAA and moved to each Workshop individually.

Summary Report of
FNCA 2009 Workshop on
Research Reactor Technology (RRT) Group

September 7-11, 2009Hachinohe, Aomori, Japan

1. IntroductionThe objective of the RRT project, "Safety Analyses of RIA (Reactivity Initiated Accident) and LOFA (Loss of Flow Accident) for Research Reactors", is to improve and equalize the level of safety analysis techniques among participating countries to assure the safe and stable operation of research reactors for the promotion of effective utilization.

The 1st workshop of the project was held in Dalat, Vietnam in October, 2008 and it was ended successfully. The subject was to exchange the information on current status of safety analyses of each country, to demonstrate how to install and execute COOLOD-N2 and explanation of sample problems.

2. SubjectsThe subject of the 2nd workshop is to exchange the information on the safety analysis result for the domestic reactor with COOLOD-N2, to demonstrate how to install and execute EUREKA2/RR and explanation of sample problems.

3. OpeningDr. Kiyonobu Yamashita, RRT Project Leader of Japan, presented the current status of the project and the fruits of project activities in 2008. He also reported the schedule of this workshop as shown in Table 1 as well as the 3 year schedule in Attachment A.

COOLOD-N2 code has been used to calculate the thermal-hydraulic parameters of TRIGA MARK-II Research Reactor of Bangladesh. Both natural convection mode (NCM) and forced convection mode (FCM) for the reactor core cooling have been studied at the steady-state operating power. The fuel temperature, cladding temperature and coolant temperature were obtained from the analyses. In NCM, the results obtained were compared with those from NCTRIGA code. The comparison shows good agreement for cladding temperature and coolant temperature while fuel temperature is seen to remain in reasonable agreement. Similarly, results from COOLOD-N2 in FCM were compared with those from EUREKA-2/RR and the results were found to be in good agreement as well. Finally, COOLOD-N2 seems working well for thermal-hydraulic analysis of the TRIGA type reactor.

Thermal-hydraulic calculation for CARR was carried out using COOLOD-N2. The detailed parameters such as power distribution, geometry information of fuel assemblies and flow channels, coolant inlet temperature and pressure are used as input data. The important parameters for steady states calculated from COOLOD-N2 had been obtained, such as the temperature distribution of fuel meat, cladding surface, bulk coolant, ONB, pressure and pressure loss of coolant, the heat flux of DNB, OFI (Onset of Flow Instability) as well as safety margin of DNBR and OFIR. The comparison of results from the output of COOLOD-N2 and CARRCO, which is developed by China, is given, and it is found that all results are satisfied for safety requirements. Since CARR has the characteristics of high coolant velocity and high heat flux, the different correlations are used in CARRCO and it is reasonable that the results from COOLOD-N2 and CARRCO are not exactly agreed. Anyway, COOLOD-N2 could be used as the reference code to analyze the steady-state parameters of CARR.

The Multipurpose Reactor of Gerrit Arnold Siwabessy (RSG-GAS), formerly called MPR-30, is a pool type reactor that uses light water as coolant and moderator. RSG-GAS is a material testing reactor (MTR) typed research reactor, that uses low enriched Uranium (19.75 w/o) fuel elements with 2.96 [gU cm-3] meat density. The reactor has 30 MW nominal thermal power and 2x1014 [n.cm-2s-1] thermal neutron flux at the central irradiation position. Presently, the silicide fuel (U3Si2-Al) is used in the core. The thermal-hydraulic analyses of the RSG-GAS core were carried out using COOLOD-N2. The investigation of the core thermal-hydraulic characteristics is focused on the safety margin of RSG-GAS using different DNBR correlations (i.e., Labuntsov correlation, Mirshak correlation, Bernath correlation, DNBR JRR package correlation and the safety margin against flow instability ratio by Interatom correlation). The MDNBR results obtained using Labuntsov correlation, Mirshak correlation and Bernath correlation and Interatom correlation gave safe margin. On the other hand, the calculation result at 30 MW showed that the MDNBR calculated by JRR-3 package less than the MDNBR safety limit of 1.5. Thus, the operation power shall be constrained to less than 25 MW. On the daily operation, the RSG-GAS is operating safely on 15 MW power level.

COOLOD code (including several versions) has been developed continuously in Japan Atomic Research Institute (JAERI, presently "JAEA"). It has been used for thermal-hydraulic analysis of JRR-4 and the results of these analyses have been utilized for the design of fuel, cooling system and so on.
In this session, analytical results of JRR-4 under several conditions were introduced. One of the analytical conditions was normal operation condition (under forced convection mode and natural convection mode) and the other was severe operating condition. From the results of these analyses, it was found that every safety criteria for the design of the research reactor was satisfied at the normal operation. On the other hand, in case of severe operating condition, it was found that there is a possibility to appear nucleate boiling at 3,850 kW forced convection operation. However, the maximum fuel meat temperature and MDNBR satisfy the safety criteria.
From these results, it was confirmed that there are no fuel plate damage at every operational conditions.

(5)

Korea"Thermal-Hydraulic analysis of a small "virtual" research reactor using COOLOD-N2" by Dr. Jonghark Park

In the 2008 FNCA meeting in Dalat, Vietnam, a thermal-hydraulic analysis code for single channel, COOLOD-N2, was introduced. The COOLOD-N2 is simple, easy to use and good for thermal-hydraulic analysis for both plate type fuel and bare rod type fuel. Korea considered applying this code to the thermal-hydraulic analysis of HANARO core, but it has some difficulties because the HANARO fuel is the finned rod type. Unfortunately the COOLOD-N2 can not be applied to the finned type rod fuel, yet. Korea decided to employ a virtual reactor to be used for thermal-hydraulic analysis using COOLOD-N2, which has a small power and employ the plate type fuel.
This is a result of performing a thermal-hydraulic analysis on a small size reactor using COOLOD-N2. A calculation was carried out to find a minimum flow velocity of coolant which is required to ensure safe operation at the given conditions. Pressure at the core inlet is fixed as 1.68 kg/cm2 due to the hydro-static head of reactor pool. In order to examine the possibility of power upgrade, thermal-hydraulic analysis was carried out for 5 MW power as well as 10 MW power. The core inlet temperature is very important value influencing directly on the safety. It can vary with ambient temperature, ultimate heat sink. Several calculations were conducted to investigate the effect of inlet temperature rise.
All results of thermal-hydraulic analysis on the small reactor were successful and they would be expected to be useful data for evaluating the safety.

Thermal-hydraulic calculation for PUSPATI TRIGA Reactor was carried out using COOLOD-N2. This code has capability in calculating fuel temperature distribution, heat transfer coefficient, coolant temperature, heat flux at onset of flow instability as well as departure nucleate boiling (DNB) heat flux. Previously, the thermal-hydraulic calculation of RTP was done by General Atomics, the manufacturer of TRIGA reactors. For the case of RTP, parameters such as cladding and fuel meat temperature, inlet and outlet coolant temperature was calculated in order to obtain the heat flux and DNBR. The Lund DNB heat flux correlation which is typically used for rod type TRIGA fuel was used to calculate the RTP heat transfer model. Since it is the first trial to run thermal-hydraulic calculation using COOLOD-N2 for the RTP, a lot of work is need to be done to obtain good results. Therefore, tutoring from the experts and helps from other country members is also necessary for deeper understanding of this computer code. Later, a validation with experiments setup will be carried out to get satisfied result and the value will be compared with GA calculation as stated in the Safety Analysis Report of PUSPATI TRIGA Reactor.

(7)

Thailand"Thermal-Hydraulic analysis of Thai Research Reactor (TRR-1/M1) using COOLOD-N2" by Mr. Chanatip Tippayakul

During 2008, the FNCA activities on RRT conducted in Thailand include the modeling of the TRR-1/M1 core using COOLOD-N2, the validation of the COOLOD-N2 model against the measurement, organizing a training course on thermal-hydraulic analysis of nuclear reactors using COOLOD-N2 and the documentation of COOLOD-N2 modeling for TRR-1/M1. First, the existing COOLOD-N2 model for TRR-1/M1 was reviewed and re-evaluated in detail. The radial peaking factors used in this model were obtained from the neutronics calculation using SRAC. Small corrections were introduced to the COOLOD-N2 input model. Subsequently, in order to validate the accuracy of the COOLOD-N2 model, experiments were set up to measure the in-core water temperature at various power levels at different axial positions of core and fuel temperature. The code-to-measurement comparisons show that the COOLOD-N2 model overestimates the measured values. However, this overestimation demonstrates the conservatism of the COOLOD-N2 model. It can thus be concluded that COOLOD-N2 is applicable for safety analysis of TRR-1/M1.
In addition, a training course on "thermal-hydraulic analysis of nuclear reactors using COOLOD-N2" was organized as part of this FNCA program. The participants were from many organizations in Thailand including TINT, OAP, universities (engineering and physics majors). This training course can be regarded as the result of knowledge accumulation from using COOLOD-N2 at TINT. Finally, the COOLOD-N2 documentation is being performed in order to preserve the knowledge and know-how in using COOLOD-N2 for safety analysis of TRR-1/M1. This assures ultimate safety to the operation of TRR-1/M1.

Dalat Nuclear Research Reactor (DNRR) is moderated and cooled by light water in natural convection mode. This pool-type reactor is loaded with 104 fuel assemblies (FAs) including two kinds of fuel assemblies: 36% enriched VVR-M2-type U-Al alloy (98 FAs) and 19.75% enriched VVR-M2-type UO2-Al dispersion fuel (6 FAs). The reactor can be operated at the maximum power of 500 kW.
Safety analyses of DNRR consist of neutronics analysis, steady-state thermal-hydraulic analysis and transient analysis. The partial core conversion was succeeded on 12 September 2007 based on some neutronic and thermal- hydraulic codes. After that, SRAC, MVP and COOLOD-N2 are used in neutronics and thermal-hydraulic calculations for the safety analysis of a conceptual core of a new 20 MW multi-purpose research reactor in Vietnam. These codes are also used for the full conversion of DNRR core from HEU to LEU fuel elements and for safety analysis report of the present DNRR core and compared with the results of other codes such as MCNP, RELAP5/MOD3.2 and PLTEMP. COOLOD-N2 code has been used to calculate the temperature distribution of current DNRR core (4-2009) and its results are in agreement with the measurement. Moreover, based on the RRT Project, EUREKA2/RR could be applied well for some calculations of DNRR core for some scenarios such as reactivity induced accident analysis and transient analysis.

6. Outline of EUREKA2/RR and Instruction of Input DataEUREKA-2/RR is a coupled neutronics and thermal-hydraulics code for the reactivity initiated accident, has been developed in order to analyze neutronic, thermal-hydraulic transient behaviors in research reactors. EUREKA2/RR adopt one point kinetic model and node-junction model (same as RELAP4). Heat transfer correlations and CHF correlations used in EUREKA-2/RR have been specially developed for research reactors in which plate-type-fuel is adopted.
EUREKA-2/RR can analyze the transient response of the core against the reactivity change caused by control rod withdrawal, coolant flow and temperature change and so on. Especially, it can well simulate fast transient behaviors in serious reactivity initiated accidents in research reactors.
In this session, there are some questions from participants, such as how to select heat transfer correlations, about interpretation of examples of calculation results, and so on. Mr. HIRANE answered these questions with other member's supports and obtained understandings of participants.

7. Demonstration of Installation and Execution Sample Program on EUREKA2/RRMr. Nobuhiko Hirane explained and demonstrated the installation and execution of EUREKA2/RR with distributed CD. The participants practiced the installation and the calculation of sample problems. Afterward, all participants compared their results of calculation with results of demonstration. It was confirmed that each calculation was finished normally, and its result agrees with demonstration. Thereafter, Mr. Hirane interpreted sample input data of EUREKA2/RR.
After the demonstration, there are some questions about how to run the program from participants and how to select output parameters in input data. Mr. Hirane helped them, and all questions were answered.

8. Current Status of Using EUREKA2/RREvery country had succeeded in installing EUREKA2/RR and executing sample program before workshop. The current status of using EUREKA2/RR are shown in Attachment C.

9. Special LectureProf. Kaichiro Mishima conducted the academic lecture regarding thermal-hydraulic analysis of research reactor.
In this lecture, the basic concept and overview of thermal-hydraulic and safety analysis were presented, covering the purpose of thermal-hydraulic and safety analysis, safety criteria, the principle of heat removal, steady-state and transient thermal-hydraulic analysis, both for plate-type and TRIGA fuels. Concerning heat transfer from fuel plates and fuel rods, boiling curve, onset of nucleate boiling (ONB), departure from nucleate boiling (DNB), critical heat flux (CHF), flow instabilities, etc. were explained, and some observation results, including video images of dryout phenomenon on the surface of heated flat plate, were presented to help better understand related phenomena. In addition, correlations to calculate heat transfer coefficients, DNB heat flux and ONB conditions were reviewed, showing some comparisons with experimental results. Furthermore, explanations were extended to peaking factors and engineering hot channel factors. Finally, the importance of code verification and validation, quality assurance and version control as well as user effects in thermal-hydraulic and safety analysis was stressed.

10. Discussions of Future PlanFor the next FNCA Workshop, Mr. Hisashi Sagawa proposed that participating members should present the safety analyses results for domestic reactor at reactivity initiated accidents and/or loss of flow accidents using EUREKA2/RR as shown in Table 2. All members agreed with the proposal. He also proposed the draft of contents of final report for this project, and all members agreed the draft.
Subsequently, the next project was discussed and themes such as simulator, NRG, mechanical stress evaluation, PSA, RI production, NTD-Si, track etched membrane, advanced research reactor design and shielding analysis, were proposed from participating members. As the results of discussion, the "Design of Advanced Irradiation Capsules" was picked up as a next project to improve and equalize the level of irradiation techniques among participating countries to assure the safe and stable operation of Research Reactors for the promotion of effective utilization. Because all member countries product Radio-isotopes and some countries have a plan to product NTD-Si. Dr. Yamashita will present this proposal in next Coordinator Meeting tentatively.
All member agreed that the next Workshop of RRT would be held in China (1st priority) or in Thailand (2nd priority).

The workshop was held successfully with participants from Bangladesh, China, Indonesia, Korea, Japan, Malaysia, Thailand and Vietnam.

2.

Each country has reported thermal-hydraulics calculation results of domestic reactors by using the COOLOD N2. It was reported that the results agreed well with their own code results or experimental data.
Bangladesh, Malaysia and Thailand have applied it for rod type fuel of TRIGA reactor. China, Indonesia, Korea, Japan and Vietnam have applied it for plate type fuel of MTR reactor. All participants are convinced that the COOLOD-N2 can be used for safety analyses of own domestic reactors.

3.

Information and experience on thermal hydraulic analyses were well exchanged among participants. Especially, the academic lecture by Prof. K. Mishima was useful and has given a wide and deep view for thermo-hydraulics of research reactors to participants.

4.

Japan demonstrated how to install and execute the common code (EUREKA2/RR). All countries have installed it and execute sample problem calculation successfully. All participants agreed to carry out the reactivity-initiated accidents and loss of flow accidents of domestic reactors with EUREKA2/RR.

5.

Design of Advanced Irradiation Capsules was proposed for theme of the next RRT-project, tentatively.

6.

All participants are convinced that the RRT-project is important for safe and stable operations as well as advanced utilizations of research reactors.

Meeting report for
FNCA 2009 Workshop on
NAA project

September 7-10, 2009Hachinohe, Aomori, Japan

Participants:

1.

Dr. John W. Bennett

Australia

national representative

2.

Dr. Imtiaz Kamal

Bangladesh

national representative

3.

Prof. Banfa Ni

China

national representative

4.

Dr. Setyo Purwanto

Indonesia

national representative

5.

Prof. Mitsuru Ebihara

Japan

project leader

6.

Prof. Motoyuki Matsuo

Japan

additional delegate

7.

Prof. Tsuyoshi Tanaka

Japan

additional delegate

8.

Prof. Michiko Fukushima

Japan

additional delegate

9.

Dr. Hideaki Matsue

Japan

additional delegate

10.

Dr. Shun Sekimoto

Japan

observer

11.

Mr. Jong-Hwa Moon

Korea

national representative

12.

Ms. Nazaratul Ashifa

Malaysia

national representative

13.

Ms. Preciosa Corazon Pabroa

The Philippines

national representative

14.

Ms. Arporn Busamongkol

Thailand

national representative

15.

Mr. Cao Dong Vu

Vietnam

national representative

16.

Dr. Sueo Machi

Japan

coordinator of Japan

The 2009 FNCA workshop on NAA project was jointly held with the workshop on RRT. During the opening session, Prof. M. Ebihara, a project leader of Japan, presented a talk entitled "Goals of the 2009 FNCA workshop on neutron activation analysis project". The session closed with the introduction of participants.
At the beginning of the NAA session, Prof. M. Ebihara presented opening remarks on the activities to be carried out during the workshop, including:

For each of the sub-projects there was to be a lead speech at the beginning and comprehensive discussion at the ending.

3.

Free discussion for the future of NAA project.

I. Country Reports on resent status of NAA using research reactorsThe following country reports were presented by each national representative, in country alphabetical order:

Australia : Dr. J. W. BennettConsiderable progress has been made over the last 12 months in commissioning the NAA facilities at the 20 MW OPAL research reactor. It has been established that the highly thermalised neutron flux and very stable output over the timescale of hours provide near-ideal conditions for NAA. Measurements of a series of synthetic multi-element standards (SMELS) have demonstrated good accuracy and reproducibility across a wide range of elements.

Bangladesh : Dr. I. KamalThe activities of NAA group can be divided into four categories: R&D work, analytical service, projects and academic collaboration. Two R&D work were: Determination of neutron capture cross sections using NAA technique using 0.0536ev rare thermal energy and 6 sediment sample collected from Bay of Bengal were analyzed using NAA and compared results with AAS.

China : Prof. B.-F. NiChina use home made K0 software to work with methodology and application of NAA. Including: 1. Study on multi-elements of sampling behavior of RM from the sample size of gram to mg range. 2. Study on foodstuff structure of north area in china including rice, wheat, drink, vegetables and meat. 3. Air Pollution source identification and trans-boundarying as well as visibility. 4. K0 values determination of some metastable nuclides. The great progress was achieved.

Indonesia : Dr. S. PurwantoFor fiscal year 2009, NAA research group in Indonesia carries on three projects, under the title : "Analysis of toxic elements on food resources", "Monitoring of environment contamination at industrial region" and "Geochemical mapping of Pulo Panjang Banten Provence". The National Seminar and Workshop on NAA has been created as a media to dissemination and making collaboration with the end users.

Japan : Dr. H. MatsueJapan Atomic Energy Agency (JAEA) has research reactors JRR-3 and JRR-4. These research reactors are mainly used for neutron beam experiments as neutron scattering technique, neutron radiograph, and prompt gamma-ray analysis. The user support systems of JAEA are under optimization though the neutron activation analysis facilities are constructed.

Japan : Dr. S. SekimotoKyoto University Reactor (KUR) will restart on early 2010. Operation of KUR until 2016 is assured. When KUR restarts, the reactor power will be lowered to 1MW, and the irradiation time extended to 4-5 hours in Pn-1, 2, 3. However, 5MW operation will be carried out in BNCT. New utilization program using KUR, introduction of PGA system and short-lived nuclides measurement system, starts.

Korea : Mr. J.-H. MoonNAA using HANARO has been applied for a variety of samples. Recently, higher detection sensitivity has been achieved by the implementation of a Compton suppression system. DNAA and PGAA are employed for the determination of uranium in some environmental samples and major constituents in steel samples produced by an industrial company, respectively.

Malaysia : Ms. N. AshifaNAA application in Malaysia is being fully utilized for several research projects and service purpose. Several research projects are conducted in close collaboration with local agency. Service analysis is given to external and internal client. Two research projects conducted through FNCA mechanism are Determination of Elemental Pollution in Marine Sediment Sample from Malaysia Coastal Area and Elemental Characterization of Various Rice Grain in Malaysian Local Market.

The Philippines : Ms. P. PabroaNAA activities for the Philippines have been limited to the use of neutron sources for the analysis of high cross section elements and the setting-up of a PGNAA facility. PNRI involvement in the project is primarily focused on the capability of the Institute to analyze environmental samples using the EDXRF and for an opportunity to analyze marine sediment samples by NAA using Research Reactors in the other member States. Past activities had been successful in forging linkages especially with our Environmental Management Bureau.

Thailand : Ms. A. BusamongkolNuclear activities at Thailand Institute of Nuclear Technology (TINT) are carried out through the utilization of a TRIGA Mark III. Its major utilization includes isotope production for industrial and medical purposes, neutron scattering experiments, gemstone enhancement and neutron activation analysis in various fields. NAA techniques used are; INAA, PGAA and PNAA/RNAA. Elemental analysis using NAA are; air pollution, heavy metal in soil and sediment, Thai silk products, nail sample and determination of toxic and nutrient minerals in Thai food.

Vietnam : Mr. C. D. VuThe application of Neutron Activation Analysis (NAA) at Dalat Nuclear Research Institute (NRI) and the equipments for this technique are presented. The NAA section at NRI includes Instrumental Neutron Activation Analysis (INAA) and Radiochemical Neutron Activation Analysis (RNAA). Besides, at NRI, there is a system of Prompt Gamma Neutron Activation Analysis (PGNAA) which is managed and exploited by Dept. of nuclear physics & nuclear electronics).

II. Progress reports by participating countries for individual sub-projectsFor each of the subprojects, a lead presentation was made in which an overview was provided and possible project goals were suggested. Presentations were then made by each of the countries that had previously expressed an interest in being involved in each sub-project.

II-1 Geochemical mapping and mineral explorationDr. J. W. Bennett (Australia) - lead presentationWe were reminded of the potential applications of geochemical mapping in mineral exploration, environmental monitoring and agriculture. Keys to success will be to set achievable and meaningful goals, involve stakeholders and end-users at all stages, set up strong project management, co-operation between participants and to publicise successes. Countries may choose to participate at a level that matches national priorities, technical capabilities and available resources.

Prof. T. Tanaka (Japan)Three areas of progress in geochemical mapping sub-project in Japan are reported.
The first is the discovery of "gold pollution" in the city area. Another area of progress has been in the accurate determination of Os and Ir in natural crustal rocks. The Geochemical Mapping Session in the Japan Geoscience Union Meeting which was held on 16-21 May 2009 marked a third area of success.

Dr. Setyo Purwanto (Indonesia)For fiscal year 2009, project with the title "Geochemical mapping of Pulo Panjang Banten Province" one that funded by Ministry of Education was being done, expected can be reported on FNCA'S meeting on 2010.

II-2 Monitoring of food contaminantsMr. J.-H. Moon (Korea) - lead presentationFood samples such as some kinds of cooked rice and red ginseng were analyzed by INAA. Toxic metals like As, Cd, Hg could not be detected from most of the analyzed samples. By the analysis of red ginseng, we found one interesting trend, which many elements are concentrated in the head part of red ginseng.

Prof. B.-F. Ni (China)Four kinds of rice (Hebei, Sichuan, Yueyang, Liaoning), wheat, Carrot, celery, Onion, Pig Liver, Shrimp and Green Tea have been selected form Market. About 30 elements have been determined by K0 method. Toxic and nutrition as well as general elements were classified. The results indicated that on big difference of the elements concentration. But there are high concentration of Se, Zn, As in liver and shrimp compare with the other food. And very high concentration of Mn in tea, 10 times higher than others.

Dr. S. Purwanto (Indonesia)During fiscal year 2008-2009, determination of toxic elements and micro-macro nutrient in foodstuff by neutron activation analysis has been done. The kind of samples are vegetables, legume, mace, and flavor. The samples had been collected from market Serpong-Banten Province. Arsenic concentration in fish and rice and also Hg concentration in fish and red chili exceed the government permission value.

Prof. M. Fukushima (Japan)Six species of edible seaweeds were analyzed by NAA and obtained the total levels of 12 elements. Also dietary fiber were separated from seaweeds, and obtained non-bioavailable levels of elements by analyzing dietary fiber.

Ms. N. Ashifa (Malaysia)Two groups of rice had been collected for elemental characterization namely cultivated and hill rice. Elements were group into essential macronutrient, micronutrient and others. Black Glutinous Rice originated from Indonesia obtained significant amount of K, Co, Cr, Fe and Zn. Husk Open and Brown Rice have high As content. Averagely high amount of Fe and Mn in rice could attribute from granite geological background.

Ms. A. Busamongkol (Thailand)Rice is the major food item to most Thai people: high nutrition, high energy, low cost and long shelf. Six select varieties of rice were bought from three major local markets in Bangkok, Thailand. Elemental composition in rice samples were analyzed by using INAA technique. Elements detected are: Al, As, Br, Cl, K, Mg, Mn & Zn. The data show that K & Mg were found higher in all samples. A toxic elements; As & Cd were found do not exceed the standard recommended by the Ministry of Public Health of Thailand.

Mr. C. D. Vu (Vietnam)The concentration of trace elements in the foodstuff samples collected by marked basket study from some locations of Hochiminh city, Ninhthuan and Lamdong provinces were analyzed by INAA, RNAA and AAS methods. The daily intake of adults in these areas were estimated and compared to those of some standards. The results show that the daily intakes are lower than the permissible limits according to Vietnam standard.

II-3 Monitoring of environmental contaminationProf. M. Matsuo (Japan) - lead presentationLead speech for overview and recent progress was made by Prof. Matsuo. Features of environmental samples were summarized and the usefulness of NAA method in these samples was emphasized. Four objectives of the project were listed. To achieve international collaboration, common sampling method and sample treatment were proposed. Core sampling was strongly recommended as a common sampling method. Two case studies in his research group were also introduced.

Dr. I. Kamal (Bangladesh)The following research works performed were presented in this session: i) Ground water contamination with arsenic in eastern region of Bangladesh ii) Comparison of analytical results of Bay of Bengal Sediments with agricultural soils of Bangladesh; iii) Monitoring of Environmental Contaminants due to Ship breaking. iv) Geochemical Mapping and Mineral Exploration in Cox's Bazar.

Ms. N. Ashifa (Malaysia)Sediment samples of Sarawak coastal area were collected from 11 sampling stations. Total of 29 elemental results were obtained from NAA procedure. All sampling sites showed high enrichment of As with several stations recorded EF value more than factor of 10. This project has provided information on current status of environmental pollution in Sarawak coastal area. Data obtained from this study will be incorporated into the Malaysian Marine Pollution Database.

Ms. P. Pabroa (The Philippines)Marine sediment samples from two sampling sites-the Manila Bay and the Sorsogon Bay- have been and will be collected to determine the trace and toxic element inputs in these two bodies of water and correlate these inputs with time using data on 210Pb dating. Studies on these sites have been conducted mainly to determine the history of pollutant inputs in the bays and assess its impact in the ecosystem (in part, its relationship to harmful algal bloom).

III. Discussion of objectives, goals and implementationAfter hearing all progress reports, a comprehensive discussion was done under the chairmanship of a subproject leader and Prof. M. Ebihara for each subproject. These discussions considered objectives, goals, potential for cooperation, work-sharing and road-mapping. In each case there was a focus on potential end-users.

III-1 Geochemical mapping and mineral explorationThe point was made often that it is vital to consult with national agencies that are responsible for resource and mineral development. The initial objectives would be to provide information on the capabilities and benefits of using NAA for geochemical characterisation and to gain an understanding of the needs of the potential end users. The eventual goal is to form strong linkages that would lead to long term projects at the national level.
A suggestion was made that a high-quality brochure could be produced by the FNCA to promote the applications and benefits of NAA in the field of geoscience. The brochure could illustrate applications in geochemical mapping and mineral exploration. NAA should be presented as an adjunct to more widely used methods such as XRF and ICP-MS and its potential role in quality control should be highlighted. Such a brochure would be helpful in the introductory phase of consultations with end-users.
A proposal was received to undertake a laboratory inter-comparison of three different types of sediment materials. The outcomes of the project would be:

a)

to demonstrate the capabilities of the participating laboratories and to understand the reason for any differences;

b)

to compare the results from different methods of NAA standardisation (k0 and relative), different k0 software tools and different techniques (e.g. XRF);

c)

to contribute data for the characterisation of three reference materials for use in geochemical mapping; and

d)

promotion of the joint capabilities of the FNCA member countries.

It is expected that a journal paper would be written.
The following countries expressed a willingness to participate in the laboratory inter-comparison: Australia, Bangladesh, China, Indonesia, Japan (involving around 5 different laboratories), Malaysia (possibly also using ICP-MS) and The Philippines (using XRF).
It was agreed by all participants that geochemical mapping using NAA has the potential to make a significant contribution to national development. It was also understood, however, that it may take some years before national geoscience agencies recognise the distinct capabilities our technique has to offer and integrate NAA into the suite of tools that are routinely used.

III-2 Monitoring of food contaminantsRepresentatives from six countries participating in the sub-project of food analysis such as China, Korea, Indonesia, Malaysia, Thailand and Vietnam, have presented the analytical results of a variety of food samples. Firstly, we discuss the elemental concentration level of the rice samples which had been selected as a common target material. Arsenic concentration in the rice samples was estimated to be less than the permissible (regulation) limit of each country. Regarding to the other toxic metals, we did not detect them by conventional INAA. However, Vietnam demonstrated that radiochemical NAA is applicable for the detection of other toxic metals such as Cu, Cd, Sb, Se and so on. In addition, the analytical results of the other food samples which were targeted by each participating countries' purpose, were discussed and compared in terms of nutritional and harmful viewpoint of human health.
Finally, the discussion was executed for the next year's FNCA workshop and tea is chosen as a common target sample, since it is so popular to the participating countries and expected to contain higher elemental contents than other plant samples.

III-3 Monitoring of environmental contaminationImplementation plan of the sub-project 3 was discussed. According to the discussion, following three objectives were reconfirmed:

a) to detect the environmental changes through core samples of marine sediments
b) to identify the level of toxic or harmful elements in sediment samples
(ex. As, Sb, Cr, Cd and so on)
c) to identify the sources of pollution in sediment samples (Natural or anthropogenic origin?)

In order to achieve the above objectives, core sampling method was agreed to detect the past environment as well as surface sampling for monitoring spatial changes of contaminants. In a few countries, 210Pb method was used to know the sedimentation rate. This method can be a common protocol among FNCA countries hopefully.
The following six countries presented recent progresses of sub-project 3: Bangladesh, Indonesia, Japan, Malaysia, The Philippines and Vietnam. Among them, Bangladesh, Indonesia, Japan and The Philippines expressed their agreement to apply core sampling method to their sediment samples. On the other hand, Malaysia and Vietnam expressed the surface sampling method due to their own situation. It was proposed that all the data should be accumulated toward the next FNCA workshop to achieve the assessment of present and past marine environmental pollution in Asian countries. Finally, construction of common mail group was proposed in order to communicate each other easily.

IV. Free discussion for the future of NAA projectAs this workshop is the second one in the three-years term of the third phase of NAA project and is held at the turning point of the term, we have discussed our future plan under the chairmanship of Prof. M. Ebihara. At the beginning of the discussion, he asked all countries to explain their stance (or attitude) toward FNCA workshop. All countries expressed very positive opinions for such requests and acknowledged that the FNCA workshop is considerably important for individual participants and their communities as well. Thus, we unanimously agreed to show our intention of continuing the NAA project within FNCA at the coordinators meeting.
Then, our discussion was focussed on the content of project. After extensive discussion, we came to the following conclusions;

a)

We choose several common target materials to which NAA is applied.

b)

Candidates of such targets materials include samples related with forensic science, herbal leaves and reference materials. Beside these new candidates, geochemical samples, food stuffs and marine sediments were also nominated.

c)

Discussion on target materials is continued by all members through web and e-mail.

The workshop was formally closed by Professor Ebihara who thanked all participants for their valuable contributions and the very positive outcomes that were achieved.

Summary Report of Wrap up Session
FNCA 2009 Workshop on
Research Reactor Utilization

September 7-11, 2009Hachinohe, Aomori, Japan

Wrap up Session < RRT and NAA joint event >

After closing each parallel Workshop, each participant all gathered together for the joint wrap up session. Dr. Sueo Machi chaired this session.

At first, Dr. Kiyonobu Yamashita, Project Leader of RRT in Japan, reported the achievements in the 2009 RRT workshop as follows;

1.

The workshop was held successfully with participants from Bangladesh, China, Indonesia, Japan, Korea, Malaysia, Thailand and Vietnam.

2.

Each country has reported thermal-hydraulics calculation results of domestic reactors by using the COOLOD-N2. It was reported that the results agreed well with their own code results or experimental data.Bangladesh, Malaysia and Thailand have applied it for rod type fuel of TRIGA reactor. China, Indonesia, Korea Japan and Vietnam have applied it for plate type fuel of MTR reactor. All participants are convinced that the COOLOD-N2 can be used for safety analyses of own domestic reactors.

3.

Information and experience on thermal hydraulic analyses were well exchanged among participants. Especially, the academic lecture by Prof. K. Mishima was useful and has given a wide and deep view for thermo-hydraulics of research reactors to participants.

4.

Japan demonstrated how to install and execute the common code (EUREKA2/RR). All countries have installed it and execute sample problem calculation successfully. All participants agreed to carry out the reactivity-initiated accidents and loss of flow accidents of domestic reactors with EUREKA2/RR.

5.

Design of Advanced Irradiation Capsules was proposed for theme of the next RRT-project, tentatively.

6.

All participants are convinced that the RRT-project is important for safe and stable operations as well as advanced utilizations of research reactors.

Next, Prof. Mitsuru Ebihara, Project Leader of NAA in Japan, reported the achievements in the 2009 NAA workshop as follows;

1.

The workshop was held successfully with participants from Australia, Bangladesh, China, Indonesia, Japan, Korea, Malaysia, Philippines, Thailand and Vietnam.

2.

In the first session, each country has reported present status of NAA using research reactors.

3.

In the second session, a lead presentation was made by each subproject leader in which an overview was provided and possible project goals were suggested for each of the subprojects, namely;
a) NAA of geochemical samples for geochemical mapping and mineral exploration,
b) NAA of food samples for contamination-monitoring, and
c) NAA of marine sediment samples for environmental monitoring.
Progress reports were presented by participating countries for individual sub-projects.

4.

After hearing all progress reports, comprehensive discussions were done for the third session. These discussions considered objectives, goals, potential for cooperation, work-sharing and road-mapping. In each case there was a focus on potential end-users.

1)

Geochemical mapping and mineral explorationA suggestion was made that a high-quality brochure could be produced by the FNCA to promote the applications and benefits of NAA in the field of geosciences. Besides, a proposal was received to undertake a laboratory inter-comparison of three different types of sediment materials.

2)

Monitoring of food contaminantsArsenic concentration in the rice samples as a common target material was estimated to be less than the permissible (regulation) limit of each country. Tea was chosen as a common target sample for the next year's FNCA workshop.

3)

Monitoring of environmental contaminationCore sampling method was agreed to detect the past environment as well as surface sampling for monitoring spatial changes of contaminants. 210Pb method that was used to know the sedimentation rate in a few countries can be a common protocol among FNCA countries hopefully.

5.

In the last session, free discussion for the future of NAA project was done. All countries expressed very positive opinions and acknowledged that the FNCA workshop is considerably important for individual participants and their communities as well. All countries unanimously agreed to show their intention of continuing the NAA project at the coming FNCA coordinators meeting.

After above 2 presentations, Dr. Machi wrapped them up as follows;

RRT

1.

COOLOD-N2 and EUREKA2/RR contribute for assurance of safety and better utilization of research reactor

2.

Training to use COOLOD-N2 and EUREKA2/RR should be also a good step to use safety codes for nuclear power plant

NAA

1.

Geochemical mapping and mineral exploration:
Active approach for collaboration with sector of mineral resources to meet national interest. Australia & Japan share experience and information with other member countries

2.

Food analysis for toxic contaminants and micro- nutrients:
A number of interesting analytical results for rice and a variety of foods were reported by 6 countries. Challenge is to have collaboration with food sector

3.

Marine sediment analysis:
Contributing monitoring seacoast pollution
Six countries reported extensive data on marine sediments, which should be fully used by controller of marine environment

4.

To prepare leaflet for end-users on characteristics of NAA complementary with XRF and ICP-MS

Closing session < RRT and NAA joint event >

Dr. Sueo Machi, FNCA Coordinator of Japan gave closing remarks and 2009 FNCA Workshop on Research Reactor Utilization that consisted of NAA and RRT was formally closed.